ML19262A410
| ML19262A410 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/09/1977 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| GQL-0287, GQL-287, NUDOCS 7910290496 | |
| Download: ML19262A410 (2) | |
Text
NRCPORM 195 U.s. NUCLE AR REGUL ATORY COMMISSION OOCKET NUMBE R (2 76) q% pao NRC DISTRIBUTION FOR PART 50 DOCKET MATERI AL w.
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Reading, Pennsylvania 19603 01-00-77 R. C. Arnold DATE RECEivEO 07-Ih 77
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DESCRIPTION ENCLOSU R E Ltr. Furnishing Tech Spec change i
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requests which have i= pact upon the ticely sta dup of 3I-1 for cycle 3...
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DO NOT REMOX_B.
ACKl(OWL 3pgD NT NAME:
THREE MILE ISLAND UNIT f 1 22 SAFETY FOR ACTION /INFORMATION rwTon ASSIGNED AD:
AR9TCWD An*
/ BRANCH CHIEF?
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PROJECT R\\ NAGER:
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INTERNAL DISTRIBUTION j
{/ PEG FIFE J SYSTEMS SAFETY PLfNT SYSTEMS SITE SAFETY &
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SCHROEDER BENAROYA DENTON & m'T T r?
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/ GOSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECU.
MIPC MACARRY KIR1"J00D ERNST CASE B03NAK BALLARD HANAUER SIL'EIL OPERATING REACTORS SPANGLER HARLESS PAULICKI STELLO SITE TEGI.
PROJECT MANAGEMENT REACTOR SAF',TY OPERATING TECH.
CAMMILL BOYD ROSS
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EISENHUT STEPP P. COLLINS NOVAK
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SHAO HULMAN HOUSTON ROSZTOCZY
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BAER PETERSON CHECK
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Btrrl,ER SITE ANALYSIS MELTZ
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METHOPOLil'AN EDISON COMPANY POST OFFICE BOX 542 READING, PENNSYLVANIA 19603 TELEPHONE 215 - 929-0601 March 9,1977 GQL 0287
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-21 Directer of IIuclear Reacter Regulation E
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Attn:
R. W. Reid, Chief u.s. we.U t n: '" ".
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Cperating Reacters Eranch :!c. k C
U. S. :iuclear Regulatory Cctrissicn Washington, D. C.
20555 Regulatorf Doc e gg w_;-
Oear Sir:
Three Mile Island :iuclear Sta* ion Unit 1 (TMI-1)
Dociet Ib. 50-269 Cperating License DFR-50 Listed belev, are all technical specifications change requests which have impact upon the timely startup cf TMI-l for cycle 3.
These are listed in cider cf importance:
Date Pricrity ?!c.
Submitted Sub'ect 1
h5 1/26/77 Cycle 3 Relcad 2
50 2/23/77 Fressure-Temperature ',1=its Reycnd 2 EFFY 3
39 10/21/T6 Trip and Relief Valve Set;cints h
51 2/28/77 Centainment Requirements 5
h9 2/18/77 Deletien of Reactor Vessel Clad In-Service Inspecticn 6
h8 2/18/7T Clarificaticn cf Integrated Leak Rate Test Requirements T
LT 2/3/77 Spent Fuel Pcci Modificati"r 3
22 h/15/76 Modification of Integrated ;esk Rate Test Requiremenca Ycur prceptness in reviewing these willite appreciated.
Sincerely, R. C. a nc1d Vice President RCA:JJM:kl
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